MCNP benchmark analyses of critical experiments for the Space Nuclear Thermal Propulsion program
- Brookhaven National Lab., Upton, NY (United States)
- Sandia National Labs., Albuquerque, NM (United States)
- Babcock and Wilcox Co., Lynchburg, VA (United States)
Benchmark analyses have been performed of Particle Bed Reactor (PBR) critical experiments (CX) using the MCNP radiation transport code. The experiments have been conducted at the Sandia National Laboratory reactor facility in support of the Space Nuclear Thermal Propulsion (SNTP) program. The test reactor is a nineteen element water moderated and reflected thermal system. A series of integral experiments have been carried out to test the capabilities of the radiation transport codes to predict the performance of PBR systems. MCNP was selected as the preferred radiation analysis tool for the benchmark experiments. Comparison between experimental and calculational results indicate very good agreement. This paper describes the analyses of benchmark experiments designed to quantify the accuracy of the MCNP radiation transport code for predicting the performance characteristics of PBR reactors.
- Research Organization:
- Brookhaven National Lab., Upton, NY (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 10160195
- Report Number(s):
- BNL--48698; CONF-930103--38; ON: DE93014046
- Country of Publication:
- United States
- Language:
- English
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210600
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100
220900
BENCHMARKS
COMPUTERIZED SIMULATION
CRITICALITY
M CODES
MONTE CARLO METHOD
NESDPS Office of Nuclear Energy Space and Defense Power Systems
POLYETHYLENES
POWER REACTORS, MOBILE, PROPULSION, PACKAGE, AND TRANSPORTABLE
RADIATION TRANSPORT
REACTOR CORES
REACTOR SAFETY
SPACE PROPULSION REACTORS
TEMPERATURE COEFFICIENT
THEORY AND CALCULATION
WATER MODERATED REACTORS